Structural modification of indium implanted glassy carbon by thermal annealing and SHI irradiation

Abstract

The structural changes, migration behaviour of indium (In) implanted into glassy carbon (GC) and the effect of annealing on radiation damage introduced by ion implantation have been investigated. The GC substrates were implanted with 360 keV indium ions to a fluence of 2.0×10 16 ions/cm 2 at room temperature (RT) and 350 °C. The RT implanted samples were isochronally annealed in vacuum between 200 and 1000 °C for 1 hour. The 350 °C implanted GC substrates were irradiated 167 MeV with Xe 26+ ions at room temperature to a maximum fluence of 5.0×10 14 ions/cm 2. The implanted GC structure was damaged and had an almost amorphized structure. Annealing of the RT implanted samples resulted in some recrystallization which increased with temperature and the diffusion behaviour of implanted In. Fickian diffusion of implanted In started after annealing at 300 °C, however, structural changes in the GC were observed after annealing at 200 °C. Annealing at 400 and 600 °C resulted in the diffusion of In toward the surface of GC accompanied by a loss of In. The SHI irradiation of the 350 °C implanted samples at increasing fluence, did not result in a detectable migration of implanted In.

Diffusion of strontium implanted in glassy carbon

“…A key property for a nuclear waste storage material is low diffusivity for the radioactive materials. Although there had been a few reports of diffusion of fission product elements in glassy carbon [17][18][19][21][22][23][24][25][26], this is the prime reason for this study, i.e. to determine the diffusivity of the radiological important fission product, strontium, in glassy carbon.…”

“…Two key factors for a material to be used in the nuclear industry are radiation hardness and diffusion properties. The radiation resistance of glassy carbon is largely unexplored with some Raman studies, see [12][13][14][15][16][17][18][19] and also with thermal conductivity measurements [20]. A key property for a nuclear waste storage material is low diffusivity for the radioactive materials.…”

Evaluation of diffusion parameters and phase formation between tungsten films and glassy carbon

“…It has high thermal stability and does not transform into graphite even at high temperatures up to 3273 K [10,11]. Glassy carbon possesses physical, chemical and mechanical properties which make it very promising for technological applications [12]. These properties include moderate hardness, resistance to corrosion and wear, high chemical inertness [13], impermeability to gases and liquids [14].…”

“…The properties of glassy carbon enumerated above have drawn the attention of many researchers to study its performance improvement by ion implantation. Notable studies on ion species implanted in glassy carbon include Co [19], Cd [11], In [12] and Cs [20]. The results of these studies showed that the diffusion patterns of the implanted ions were not into the bulk, but rather towards the surface of the glassy carbon damaged by ion implantation.…”

The effect of irradiation with swift heavy ions on the structural and morphological properties of beryllium oxide ceramics

“…Studies on radiation resistance of beryllium and its oxide to neutron radiation originate in the middle sixties of the XX century [16,17]. At the same time, most data on radiation resistance cannot be compared with each other due to variety of sample types (single crystals, polycrystals, samples with different impurities), which is related to obtaining methods as well as to difference in operating parameters of nuclear reactors [18][19][20]. In the course of previously conducted studies, a procedure was developed for comparing different types of radiation, which is based on measuring changes in structural parameters, defect concentration in the structure and magnitude of atom displacements from lattice sites [21][22][23].…”